ML17261A106

Forwards List of Piping Lines Inside Containment Which Normally or Occasionally Experience High Energy Svc Conditions.Distinguishes Lines Which Do Not Need to Be Considered for Systematic Evaluation Program Topic III-5.A

ML17261A106
Person / Time
Site:	Ginna
Issue date:	02/09/1979
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:	Ziemann D Office of Nuclear Reactor Regulation
References
TASK-03-05.A, TASK-3-5.A, TASK-RR NUDOCS 7902200034
Download: ML17261A106 (8)

Text

ATTACHMENT 2 February 9,

1979 Director c= Nuclear Reactor Regulation AT1:

Nr. Denris Ziemann, Chief Operatirg Reactors Branch

>2 U.S. Nuclear Regulatory Commission washington, D.C.

20555 Dea:1r.

niemann:

Subject:

SEP Topic iiI-5.A, High Energy Line Breaks Inside Containment Rochester G'as and Electric has precared a list of piping lires inside the containment which normally or occasionally experience high energy service conditions.

The listing is enclosed as Attachment A.

This listing distinguishes between those lines which need not be considered for SEP Topic EiZ-5.A because of line size, regulatory position SRP 3.6-1 or normal operating conditions and those lines, or portions of lines, wnich merit further'onsideration.

Wlestinghouse has reviewed tnis list and plans to inspect the containment building along with RGGE auring our upccmirg refueling outage to identify any locations where potential high energy line breaks might have deleterious conse-cuences.

Ne expect that we may be able to eliminate additional lines frcm further consideration in Topic IZl-5.A as a result of this inspection and review.

This approach to resolution of tne Topic generally corresponds to approach numhe" 2 as identified ir.

an attachment to a letter cated Septembe 7,

1978 rcm Darrell Eisenhut.

Our refueling outage 's scheduled to beg'n February 10, 1979 and last through m'd LMarch.

fvestinghouse has reviewed orig'nal analyses pe fczmed cr certain piping inside contairment ard is ccmpletirg a summary report.

he ant'cipate heing able to provide that summary repoz to you hefo e the end of rebzuary.

Basec on s ress analyses and tne results or cuz inspect'ns insice containment we expect to be able to discuss a specific program for zesolving the remaining piping systems issues.

Resolution may include insezvice ins"ec 'on or detailed ara hays's.

S'c rely yours, At=achment

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Attachment A

LIVES PENETRATING CONTAIN."IENT

'WHICH NOR'1ALLY OR OCCASIONALLY EXPERIENCE HIGH ENERGY SERVICE CONDITIONS Line Penetra-Size tion No.

(inches)

Normal iiaximum Designation Operating Conditions Press(osi)

Temn( E)

Remarks

" Indicates those lines to be considered for potential high ene gy line breaks C Indicates normal maximum'emperature is less than 200 F

120 102 Accumulator N~

700 C

2

"-Charging (Alt.)

2250 C

vented during normal operation no jet or whip upstream of check valve 383A; consider only line between RCPB and valve 383A 140 10

-"RHR-out 360 350 consider only RCPB to valve 700, see SRP 3.6-1 108 RCP seal water-

<100 out 200 normally operated

<200~,

alarmed at 190o 106 110 110 Bot 3/4 "RCP seal water-in 2250

-RCP seal wate -in '250 Accumulator test 1500 normally depressurized except during test

'12 "Letdown 600 380 higher pr ssure and tempe ature upst earn o-ori ices and reoener-tive heat exchanger 100

"-Charging 2250 higher temperature downstream of regenerative heat exchanger

?age 1 or

"=

."- bruarr 9, 1979

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LIVES PENETRATING CONTALVi1ENT

%LICH NOR<ILLY OR OCCASIONALLY EXPERI~VCE HIGH ENERGY SERVICE CONDITIONS Penetra-tion No.

Line Size (inches)

Normal

.'maximum Designation Operating Conditions Press(osi)

Temp(~F)"

Remarks

": Indicates those lines to be considered for potential high energy line breaks C Indicates normal maximum temperature is less than 200 F 206 3/8 Sample-Pressurizer 2250 650 liquid eliminate because of size 206 205 207 3/8 Sample-RCS HL 2250 650 3/8 Sample-Pressurizer 2250 650 steam 3/8 Sample-SG 1000 550 eliminate because of size eliminate because of size eliminate because of size 207 301 303 322 321 402 403 404 30

":~dain Steam 14

':Feedwate 14

"-Feedwater 10 "RHR-in 3/8 Sample-SG Unit Htr Steam Unit Htr Steam 2

""SG Blowdown 2

-SG Blowdown 30

"-Main Steam 1000 550 150 340 150 340 1000 550 1000 550 1000 550 1000 550 1000 430 1000 430 360 350 eliminat because of size not used when plant is hot not used when plant is hot consider only RCPB to valve 721, see SRP 3.6-1 lloaa20

"Standby Aux Feed 1000 430 consider onlv main e dwate

ne to check valves 9705 AhB Pace 2 of 3

."-ebruar r 9, 19"9

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LINES INSIDE CONTAINMENT BUT NOT PENETRATING CONTAINMENT WHICH NORiALLY OR OCCASIOifALLY EZPERIENCE HIGH ENERGY SERUICE CONDITIONS Line Designation Size System Normal Maximum Conditions Press( si)

Temo(oF)

Remarks

"" Indicates "hose lines to be considered for potential high energy line breaks C Iadicates normal maximum t mperature is less than 200OF

':Accumulator aad Braach Lines

-Auxiliary Spray 2ll RCS SI CUCS 2250 700 2250 600 350 consider SI branch lines be"een RCPB aad the first check valves consider only 2" braach lines to RCDT to valves

'44A 6 B.

'".Pressurizer Surge 10" RCS 2250 650 Pressurizer Spray 3 II RCS 2250 650 Pressurizer Deadweight 1/8" RCS 2250 650 eliminate because of size Tester Tube Flange Leakoff Excess Letdown ROP N2 Lines 3/8-3/4 3/4 RCS RCS ROP 2250 2250 800 600 eliminate because of size 600 iimiaate because of si e

C el'miaate because or size

-Reactor Coolant Svstem pip-'ag breaks are being evaluated unde" generic topic A2, Asymmetric Loads.

Pace 3 oz February 9, 979

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